05000455/LER-2011-002, For Byron Station, Unit 2, Regarding Containment Pressure Not within Limits Longer than Allowed by Technical Specifications Due to Personnel Error
PLA-7384, Proposed Amendment No. 292, Temporary Change to Allow Replacement on Unit 1 480 V Ess Load Center Transformers in Unit 2 Technical Specifications 3.8.7 and 3.7.1
3F0515-05, Technical Specifications Bases Control Program
CP-201500034, Licence Amendment Request 14-002, Extension of Containment Leakage Rate Testing Program
NL-14-046, Response to Request for Additional Information Regarding Containment Integrity Analysis
NL-13-002, Proposed Technical Specification Bases Changes to Credit Four Fan Cooler Units in Containment Integrity Analysis
NL-13-003, Proposed Technical Specification Changes Regarding RWST Temperature and Containment Pressure in Containment Integrity Analysis
ULNRC-05888, Response to Request for Additional Information Pertaining to Revision of Technical Specification (TS) 3.3.6, Containment Purge Isolation Instrumentation, LDCN 09-0040
PLA-6828, Eleam Electric Station, Response to E-mail (Dated March 16, 2012) Request for Additional Information on Proposed Amendment Number 281 to Unit 2 Operating License No. NPF-22
L-2011-498, Units, 3 & 4 - 10 CFR 50.59 Summary Report of Changes, Tests and Experiments for Period Covering 12/04/2009 Through 05/16/2011 and Updated Technical Specification Bases
NRC 2011-0021, License Amendment Request 262 Revision to Technical Specification Operating Limits to Include Measurement Uncertainty
TSTF-16-09, Technical Specifications Task Force - Revision 3 of TSTF-551, Revise Secondary Containment Surveillance Requirements
TSTF-14-18, Transmittal of TSTF-551, Revision 0, Address Transient Secondary Containment Conditions
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 2 of 8
NL-14-121, Indian Point, Unit 2, Updated Final Safety Analysis Report (Ufsar), Revision 25, Technical Specification Bases List of Effective Sections
TSTF-12-11, Transmittal of TSTF-540, Revision 0, Provide Completion Times in Lieu of Immediate Shutdown (RITSTF Initiative 6)
NL-11-1812, Edwin I. Hatch, Unit 1 - Technical Requirements Manual
NL-10-107, Indian Point 2 (IP2) Nuclear Power Plant Amendment Update to the Final Safety Analysis Report (Fsar), Revision 22, Improved Technical Specifications Bases
RS-08-161, Braidwood, Units 1 and 2 - Technical Specification Bases
L-2008-245, Transmittal of 10 CFR 50.59 Summary Report of Changes, Tests and Experiments Made Without Prior Commission Approval for Period 12/09/06 - 05/11/08
PLA-6328, Proposed License Amendment No. 299 for Unit 1 and Proposed License Amendment No. 269 for Unit 2 for Changes to Technical Specifications 3.6.4.1 Secondary Contaminant and 3.6.4.3 Standby Gas Treatment System
L-07-017, License Amendment Requests Nos. 334 and 205
WBL-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual
NRC Generic Letter 91-08, Removal of Component Lists from Technical Specifications
TSTF-19-05, Transmittal of TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
RA-19-0308, Clean Technical Specifications Pages Regarding Application to Adopt TSTF-425, Revision 3
PLA-5922, Proposed License Amendment Numbers 263 for Unit 1 & 228 for Unit 2 for a One-Time Change to TS 3.6.4.10 & 3.6.4.3, Completion Time for Secondary Containment & Standby Gas Treatment Subsystems Supplement No. 1
PLA-5734, Proposed License Amendment Numbers 263 for Unit 1 and 228 for Unit 2 for a One-time Change to Technical Specifications 3.6.4.1 and 3.6.4.3, Completion Time for Secondary Containment and Standby Gas Treatment Subsystems
L-PI-04-017, Development and Qualification of a GOTHIC Containment Evaluation Model for the Prairie Island Nuclear Generating Plants
L-14-343, Response to Request for Additional Information Regarding License Amendment Request to Extend Containment Leakage Rate Test Frequency
NL-03-1140, Changes to Technical Specification Bases
NRC 2003-0033, Technical Specification Bases Revisions
RS-20-010, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR)
NRC 2002-0080, Response to Request for Additional Information License Amendment Request 223 Technical Specification LCO 3.6.4, Containment Pressure
NRC 2002-0071, Response to Request for Additional Information for License Amendment Request 223 Technical Specification LCO 3.6.4, Containment Pressure
NRC 2002-0004, License Amendment Request 223 Re Containment Pressure
RBG-45935, Part B - Revisions 58 -76 to River Bend Station Technical Requirements Manual & Technical Specification Bases
05000395/LER-1983-011, Forwards LER 83-011/03L-0.Detailed Event Analyis Encl
05000395/LER-1982-064, Forwards LER 82-064/03L-0.Detailed Event Analysis Encl
ND-20-0668, Request for License Amendment for Vacuum Relief Valve Technical Specification Changes (LAR-20-005)
05000461/LER-1998-012, Forwards LER 98-012-00, High Differential Pressure Required to Close Excess Flow Check Valves Results in Valves Being Outside of Design Basis of Plant, IAW Requirements of 10CFR50.73
RC-97-0190, Forwards Response to NRC Ltr Re Violations Noted in Insp Rept 50-395/97-07.Corrective Actions:Internal Operations Memo Was Issued to Direct Operators to Ensure H Monitor Containment Isolation Valves Remained Closed Pending Review
NSD-NRC-97-5485, Forwards Responses to FSER Open Items on AP600.Summary of Encl Responses Provided in Table 1
3F0797-21, TS Change Request 209,Rev 1 for License DPR-72,adding EDG Kilowatt Indication to post-accident Monitoring Instrumentation to Support CR-3 Restart Issue of EDG Load Mgt
U-601118, Proposed Tech Specs Re Administrative Controls
NL-21-1017, License Amendment Request to Revise Technical Specification 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure
AECM-87-0201, Application for Amend to License NPF-29,changing Tech Specs to Support Design Change to Divisional Power Supplies for RWCU Sys Containment & Drywell Isolation Valves.Fee Paid
AECM-89-0051, Application for Amend to License NPF-29,allowing One Time Exceptions to Tech Spec 3.0.4 to Support Upcoming Third Refueling Outage.Fee Paid
AECM-89-0038, Application for Amend to License NPF-29,allowing one-time Exceptions to Tech Spec 3.0.4 in Lieu of Much Broader Scope Changes Associated W/Generic Ltr 87-09
AECM-88-0218, Submits Addl Info Re 880819 Application for Amend to License NPF-29,per NRC 881006 Request.Proposed Administrative Changes to Fire Protection Specs Per Generic Ltr 87-09, Included in Amend Request
AECM-84-0229, Forwards Program Completion Rept Re Conclusion of Tech Spec Review Program.Rept Documents That Thorough & in-depth Engineering,Operations & Licensing Review of Tech Specs Conducted Per Programmatic Commitments
L-94-025, Ter,Audit of Plant Specific License Conversion to STS: Crystal River Unit 3
AECM-83-0453, Forwards Summary of NUREG-0737 Tech Spec Status Per Generic Ltr 83-02.Two Required Changes Re Safety Relief Valve Challenges Will Be Submitted for Consideration by 830901
RBG-40935, Responds to Violations Noted in Insp Rept 50-458/94-18. Corrective Actions:Relief Valve 1E22 RVF039 Was Verified to Have Been Seated & Leak Tight by Evidence of Sys Pressure Observed on Other Valves within Test Boundary
RBG-40773, Forwards Interim Relief Request 03,requesting Temporary Relief to Extend Test Frequency & Postpone Testing Required by ASME Section XI,IWV-3521 & IWV-3522 for Inboard Drywell Isolation Check Valve
RBG-39894, Application for Amend to License NPF-47,revising TS for Removal of Component Lists,Per Generic Ltrs 91-01 & 91-08
PY-CEI-NRR-1559, Forwards Addl Info & Addl Change Re 920929 Emergency TS Change Request for RCIC & RWCU Outboard Valves to Address Questions Raised During Recent GL 89-10 NRC Insp on Capability of E51-F064 & G33-F004 Valves
PY-CEI-NRR-1550, Requests Emergency Change to Requirements of TS 3.6.4, Containment Isolation Valves Due to Declaration of RCIC & RWCU Sys Outboard Containment Isolation Valves,Per 920912 W/ NRR & Region III
PY-CEI-NRR-1541, Suppl to 920619 Application for Amend to License NPF-58, Removing Addl Ref to Table Numbers of Component Lists Relocated,Per GL 91-08,from TS 3.6.4 & 3.8.4.1 to Operations Manual
PY-CEI-NRR-1547, Requests Temporary Waiver of Compliance from TS 3.6.4,Action a.2 Re RCIC & RWCU Valves.Request Necessary Due to Declaration of RCIC & RWCU Sys Outboard Containment Isolation Valves as Inoperable for Closure,Per GL 89-10
PY-CEI-NRR-1848, Responds to NRC Re Violations Noted in Insp Rept 50-440/94-09 on 940422-0527.Corrective Actions:Change to Integrated Operating Instruction (Ioi) 1, Cold Startup Completed on 940717
PY-CEI-NRR-1756, Forwards Annual Rept of 10CFR50.59 Safety Evaluations for 1993
RA-22-0137, Subsequent License Renewal Application Response to ONS SLRA Second Round RAI 4.6.1-1a
PLA-4428, Forwards Application for Amends to Licenses NPF-14 & NPF-22, Revising TSs Re HPCI Pump Automatic Transfer to Suppression Pool Logic Elimination
AEP-NRC-2014-51, Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent with Previously Licensed Conditions (TAC No. MF2916), Dated May 6, 2014
05000395/LER-1983-018, Forwards LER 83-018/03L-0.Detailed Event Analysis Encl
RBG-40771, Submits Interim Relief Request Re one-time Temporary Relief Extending Test Frequency & Postponing Testing Required by ASME
1CAN031306, License Amendment Request, Adoption of Technical Specification Task Force (TSTF)-431, Revision 3 Change in Technical Specifications End States (BAW-2441)
L-08-236, License Amendment Request No. 08-006, Replacement of Beaver Valley Unit No. 2 Spray Additive System by Containment Sump Ph Control System
AECM-90-0135, Application for Amend to License NPF-29,revising 900427 & 0705 Applications Re Changes to Tech Spec Due to Addition of Alternate DHR & Addressing NRC Concerns Re Manual Realignment of LPCI Emergency Core Cooling Subsystems
L-2007-095, CFR 50.59 Summary Report, Changes, Tests, and Experiments Implemented as Allowed by 10 CFR 50.59 for the Period Covering June 13, 2005 Through December 9, 2006
05000416/LER-1987-011, :on 870729,discovered That Two motor-operated Containment Isolation Valves Used in Series at Containment Penetration 87 Shared Same Divisional Power Source.Caused by Incomplete Follow Through on Design Change
05000440/LER-1987-062, :on 870828,RHR Head Spray Containment Isolation Valve Energized in Violation of Tech Spec 3.6.4.Caused by Personnel Error.Operator Involved Counseled Re Need for Greater Attention to Detail
05000461/LER-1987-032, :on 870604,operations Dept Determined That Stroke Time Test Surveillance Required by Tech Spec 4.6.4.1 Not Performed for Containment Isolation Valve.Caused by Operations Personnel Error.Valve Deactivated
05000440/LER-1987-061, :on 870830,Tech Specs Violated When Inner Air Lock Door Not Maintained Closed W/Outer Air Lock Door Inoperable.Caused by Bushing Failure.Bushing Replaced & Design Change for Air Lock Door Initiated
05000374/LER-1999-001-07, :on 990804,failure to Comply with Suppression Chamber - Drywell Vacuum Breaker TS Action Statement Was Noted.Caused by Mgt Deficiency.Permanent Procedure to Visually Verify Vacuum Breaker Closed Was Written
05000440/LER-1986-007, :on 860414,RWCU Sys Outboard Containment Isolation Valve Rendered Inoperable by Removing Jumper Supplying Power to Closing Circuit.Caused by Use of Out of Date Drawing.Procedure Revised to Clarify Review
05000440/LER-1986-051, :on 860818,discovered That RHR Containment Upper Pool Cooling Isolation Valves Did Not Receive Reactor Vessel High Pressure Isolation Signal as Stated in FSAR Table 6.2-32.Surveillance Instruction Revised
05000440/LER-1986-057, :on 860903,containment Isolation Valves Not Deactivated in Closed Position.Caused by Failure of Nonconformance Rept Program to Require Routing of Environ Qualification Deficiencies to Control Room.Program Revised
NSD-NRC-98-5554, Forwards W Responses to FSER Open Items on AP600.Summary of Enclosed Responses,Fser Open Item Number,Associated Oits Number & Status to Be Designated in W Status Column of Oits Encl in Table 1
05000416/LER-1986-017, :on 860430,wrong Fuse Pulled During Attempt to Deactivate Containment Isolation Valve Causing Actuation of Combustible Gas Control Subsystem A.Fuse Reinserted & Sys Returned to Standby.Operator Disciplined
05000440/LER-1986-005, :on 860421,0510,17 & 19,control Room HVAC Sys Shifted to Emergency Recirculation Mode Due to High Chlorine Gas Monitor Trip Signal.Caused by Defective Optical Lamp Filament.Lamp Replaced
05000458/LER-1986-006, :on 860110,discovered Maint Activities Performed on Feedwater Testable Check Valve W/O Performance of Operability Test Prior to Returning Valve to Svc.Caused by Personnel Error.Valve Successfully Tested
05000373/LER-1996-010, :on 960829,violations of TS & Design Basis Occurred.Caused by Inadequate Standards for TS Clarification.Deleted Clarifications in Question on 960829 & Revised One Clarification
05000416/LER-1985-038, :on 850925,actuation of Standby Gas Treatment Sys a & Control Room Fresh Air Unit a Occurred Due to Reduced Voltage Output.Caused by Failed Transformer Internal.Failed Solenoid Replaced
05000395/LER-1985-020, :on 850820,containment Isolation Valve XVK-1633B Restored to Svc W/O post-maint Testing.Caused by Personnel Error.Testing on 850820 Showed Satisfactory Results.Procedures to Be Revised
05000373/LER-1996-010-06, :on 960829,determined Conditions Outside of Design Basis.Caused by Inadequate Standards for TS Clarifications.Implemented Development of TS Clarifications & Evaluates TS Interpretations
05000458/LER-1992-012, :on 920721,identified 18 Containment Isolation Valves Which Could Not Be Included in ILRT Program,Per 10CFR50,App J as Required by TS 3.6.4.Caused by Procedural Guidance.Valves Seat Leakage Tested
05000440/LER-1992-015, :on 920701,HPCS Sys Declared Inoperable Due to Inoperability of Suppression Pool Suction Valve.Daily Instruction Written to Remind Personnel to Hold Control Switch in Appropriate Position
05000440/LER-1992-008, :on 920415,loss of Administrative Control of Containment Isolation Valve Resulted in TS Violation.Caused by Inadequate Procedures.Standing Order Issued to All Licensed & Nonlicensed Operators
05000395/LER-1992-002, :on 920128,discovered That Sample Return Line from Radiation Monitor Temporarily Opened & Containment Phase a Isolation Valve Would Not Close.Caused by Personnel Error.Valve Repaired & Returned to Svc
05000289/LER-1995-001-01, :on 950307,RC Leak Caused by Failure of Parker Hannifin Compression Fitting Due to Insufficient Tightening During Installation.Shut Root Valves & Stopped Leak
05000416/LER-1983-168-03, /03L-0:on 831023,during Attempts to Operate RCIC Steam Line Warmup Valve F076,breaker Repeatedly Tripped.Caused by Burnt Off Insulation on Motor Winding. Motor Rotated Out of Insulation
05000373/LER-1983-058-01, /01T-0:on 830621,primary Containment Vacuum Breaker 1PC001D Isolation Valve 1PC003D Found Closed & Unlocked.Caused by Shortfall in Administrative Control of Equipment.Equipment Procedure Revised
05000395/LER-1983-062-03, /03L-0:on 830611 & 12,reactor Bldg Purge Exhaust Radiation Monitor Sample Pump Overload Protector Tripped. Caused by Loose Motor Controller Electrical Connections & Defective Pump Bearing.Bearing Replaced
05000395/LER-1983-018-03, /03L-0:on 830306,while in Mode 1,nuclear Sampling Sys Valves 9398 A,B & C Failed to Close During Initial Performance of Accelerated Test Program.Caused by Crud Buildup on Valve Seats.Crud Dislodged & Switch Repaired
05000395/LER-1983-046-03, /03L-0:on 830520,sampling Line from Pressurizer Valve XVX-9357-SS Indicated Intermediate Position.Caused by Out of Adjustment Limit Switches on Valve.Switches Adjusted
RBG-47169, Unit 1, Revisions to the Technical Requirements Manual and the Technical Specification Bases
05000395/LER-1983-011-03, /03L-0:on 830208 & 17,during Mode 1 Operation, Nuclear Sampling Sys Valves 9398 A,B & C Failed to Close. Caused by Limit Switch Failure on One Valve & Crud Buildup on Other Valve Seats.Crud Dislodged.Limit Switches Repaired
05000440/LER-1993-018, :on 931104,TS Violation Occurred Due to Installation Deficiencies for Target Rock Valves.Target Rock SOVs Inspected & Affected Valves Repaired & Retested.Maint Personnel Trained
05000440/LER-1990-028, :on 901009,failure to Perform Surveillance Resulted in Inoperable Containment Isolation Valves
05000440/LER-1993-004, :on 930121,MOV Testing of Main Steam Line Drain & Bypass Outboard Isolation Valve Indicated That Thrust Less than Design Thrust to Close Valve Under Accident Conditions. Review,Per GL 89-10 in Progress
AECM-90-0056, Application for Amend to License NPF-29,changing Tech Specs to Address Addition of Alternate DHR Sys & Manual Realignment of LPCI Emergency Core Cooling Subsystems During Plant Shutdown
CP-202200355, Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002
05000395/LER-2019-002, Regarding Condition Prohibited by Technical Specification 3.6.4
CP-200801015, Technical Specification Bases for Comanche Peak Steam Electric Station Units 1 & 2
05000250/LER-1998-007-02, :on 981020,containment Purge Supply,Valve Opened Wider than TS Limit.Caused by Improper Setting of Mechanical Stops.Incorporated Improved Standard Method of Measuring Angular Valve Position Into Sp.With
05000250/LER-1997-003-01, :on 970410,mode Changed W/O Meeting Requirements of TS 3.0.4 Due to Inadequate Procedural Guidance.Night Order Was Issued to Inform Personnel That S/G Blowdown Keylock Switches Were Left in Drain
05000390/LER-1917-007, Regarding Multiple Unreported Potential Loss of Safety Function Events Associated with Inoperable Single Train Systems Due to Misinterpretation of Reporting Guidance
BW160033, 2016 Braidwood Initial License Examination; Outline Submittal: Forms 401-2, 401-3; 301-1; 301-2; ES-D-1 Sheets
L-2016-116, Response to Request for Additional Information Regarding License Amendment Request 236, Revision to TS to Adopt Risk Informed Completion Time TSTF-505, Revision 1,Provide Risk-Informed Extended Completion Times
TSTF-15-07, Transmittal of TSTF-551, Revision 1, Revise Secondary Containment Surveillance Requirements
1CAN121403, License Amendment Request Supplemental ANO-1 Adoption of TSTF-431, Revision 3, Change in Technical Specifications End States (BAW-2441)
TSTF-16-07, Technical Specifications Task Force - Revision 2 of TSTF-551, Revise Secondary Containment Surveillance Requirements
RS-17-029, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control
2CAN031303, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-422, Revision 2 ‘‘Change in Technical Specifications End States (CE NPSD-1186)
RS-12-223, License Amendment Request to Revise Technical Specification 3.3.6, Containment Ventilation Isolation Instrumentation
05000397/LER-2011-004, Regarding Secondary Containment Low Differential Pressure Due to Ice Buildup
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
05000250/LER-2008-003, Regarding Inoperable Steam Generator Blowdown Containment Isolation Valve in Excess of Technical Specification Required Isolation Time
TSTF-10-04, Transmittal of TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month
05000395/LER-2007-002, Re Failure to Follow Administrative Controls Results in LCO 3.6.4 Violation
LIC-07-0082, License Amendment Request (LAR) Permanent Use of Sodium Tetraborate as the Containment Building Sump Buffering Agent
TSTF-07-24, TSTF-431, Revision 2, Change in Technical Specifications End States (BAW-2441)
TSTF-06-26, Submittal of TSTF-431, Revision 1, Change in Technical Specifications End States (BAW-2441)
05000397/LER-2005-001, Re Potential Breach of Secondary Containment Following Seismic Event
DCL-04-141, Response to 09/08/2004 Request for Additional Information Re License Amendment Request 03-18, Revision to Technical Specifications 5.5.9. Steam Generator (SG) Tube Surveillance Program. & 5.6.10
05000250/LER-2003-006, From Turkey Point Unit 3 Regarding TS Required Shutdown Due to Inoperable Containment Isolation Valve Cv 3-200B
ET 02-0030, Operating Corporation Revision to Technical Specification 3.6.3, Containment Isolation Valves
3F0502-06, Technical Specifications Bases Control Program
ULNRC-05654, Proposed Revision to Technical Specification 3.3.6, Containment Purge Isolation Instrumentation, (License Amendment Request LDCN 09-0040)
DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term. Part 1 of 8
CP-201000212, Technical Specifications Bases for Comanche Peak Steam Electric Station, Units 1 and 2
RS-12-033, Additional Information Supporting Request for License Amendment Regarding Measurement Uncertainty Recapture Power Uprate
RNP-RA/03-0061, Transmittal of TS Bases Revisions
JSP-078-92, Application for Amend to License NPF-62,changing TSs to Delete Component Lists,As Recommended in Generic Ltr 91-08 & Deleting Reactor Vessel Specimen Withdrawal Schedule,As Recommended by Generic Ltr 91-01
DCL-18-100, License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology
WO 04-0030, Revision to Technical Specification 3.6.3, Containment Isolation Valves
NL-24-0417, License Amendment Request: Shutdown Actions Mode Change Restrictions
NL-16-109, Indian Point 2 Improved Technical Specifications Bases
TSTF-19-10, Transmittal of Errata Changes to TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position
NSD-NRC-97-5263, Forwards W Responses to Comments on AP600 TS Re Containment Sys.Response to Question 68 Re TS 3.6.9 for Ph Adjustment, Is Still in Progress W/Completion Scheduled for 970825
05000387/LER-2015-013, Regarding Loss of Differential Pressure in Zone I of Secondary Containment Due to Solenoid Valve Failure
L-2016-084, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-422, Revision 2, Change in Technical Specifications End States
05000461/LER-1987-039, :on 870715,review Determined That Control & Power Circuit for Valve Not Worked Under Maint Work Request C52962.Caused by Personnel Error.Valve 1VR001B Declared Inoperable
05000440/LER-1994-013, :on 940518,noted That LPCI C Loop Injection Valve Was Closed Due to Program Weakness.Suspended Core Alternations from Time Valve Was Discovered Until Compliance W/Ts 3.6.4 Action Requirement
NL-17-0534, Joseph M. Farley Nuclear Plant, Technical Specifications Bases
PLA-7733, Correction of Technical Specification Typographical Error for TS 3.6.4.1 (PLA-7733)
RA-25-0014, License Amendment Request to Adopt the Full Spectrum Loss of Coolant Accident Methodology and Axiom Fuel Cladding Topical Reports and Associated 10 CFR 50.46 Exemption Request for Use of Axiom Fuel Cladding